05000446/LER-1995-001, :on 950203,ASME Section XI Surveillance Was Missed Due to Less than Adequate Work Documents.Revised Applicable Work Documents & Reinforced Expectations W/Cognizant Individuals
| ML20080R502 | |
| Person / Time | |
|---|---|
| Site: | Comanche Peak  |
| Issue date: | 03/06/1995 |
| From: | Flores R, Kelley J TEXAS UTILITIES ELECTRIC CO. (TU ELECTRIC) |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| LER-95-001, LER-95-1, TXX-95063, NUDOCS 9503090338 | |
| Download: ML20080R502 (6) | |
| Event date: | |
|---|---|
| Report date: | |
| Reporting criterion: | 10 CFR 50.73(a)(2)(i) |
| 4461995001R00 - NRC Website | |
text
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- 2: -f sammuummes Log # TXX-95063 i
- - File # 10200 7]
Ref. # 10CFR50.73(a)(2)(i)
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7EFELECTR/C March 3. 1995 C. Imce Terry armp vico rresuem U. S. Nuclear Regulatory Commission Document Control Desk Washington. DC 20555-
SUBJECT:
COMANCHE PEAK STEAM ELECTRIC STATION (CPSES) - UNIT 2 DOCKET NO. 50-446 CONDITIONS PR0HIBITED BY THE PLANT'S TECHNICAL SPECIFICATIONS i
LICENSEE EVENT REPORT 446/95-001-00 Gentlemen:
Enclosed is Licensee Event Report (LER) 95-001-00 for Comanche Peak Steam Electric Station Unit 2. " Missed ASME Section XI Surveillance Due to less i
than Adequate Work Documents" I
1 Sincerely.
C. L. Terry N
By: 3. J. Kelley Vice President of Nuclear Engineering and Support OB:cc Enclosure cc:
Mr. L. J. Callan. Region IV Mr. D. D. Chamberlain. Region IV Resident Inspectors CPSES l
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- - Enclosure to TXX-95063
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SUMMARY OF THE EVENT, INCLUDING DATES AND APPR0XIMATE TIMES On February 3. 1995, during package review, the Inservice Test Coordinator discovered that a portion of surveillance testing per T.S.
4.0.5 for Main Steam check valve 2MS-0143 had not been performed between February 16, 1994 and August 3. 1994. Although, monthly Technical Specification required testings had been performed on this valve the required quarterly ASME Section XI surveillance test for the valve in the closed direction was not performed in May 1994. This surveillance was missed when the normal frequency was interrupted by the Unit 2 Mid Cycle Outage. and steam to run the Turbine Driven Auxiliary Feedwater Pump was not available.
After the Unit 2 Mid Cycle Outage surveillance testing for the Auxiliary Feedwater System was required for valve 2MS-0143.
However, the crew reviewing the surveillance work order (SWO) questioned which part or parts of the SWO were required to be performed. The SWO contains both
" monthly" and " quarterly" tests for multiple components, the " monthly" tests are for the T.S. requirements whereas the " quarterly" tests are for ASME Section XI.
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The Operations Outage Duty Manager (utility licensed) recognized that' all com)onents listed within the SWO had to be tested.
Upon review of applica)le testing procedure section for the AFW system, the Operations Outage Duty Manager concluded that completion of section 8.1.6 would fulfill the requirements of section 8.1.3, as the components and Technical Specifications listed in section 8.1.3 are contained in section 8.1.6.
This was documented in the SWO and the test performed. However, the Operations Outage Duty Manager overlooked the fact that section 8.1.6 does not test check valve 2MS-0143 in the closed direction.
Hence, the required ASME section XI surveillance which was delineated in section 8.1.3 was not performed.
E.
THE METHOD OF DISCOVERY OF EACH COMPONENT OR SYSTEM FAILURE, OR PROCEDURAL OR PERSONNEL ERROR During a post-work review of work packages the IST Coordinator noted that the required surveillance for a main steam check valve was not satisfied.
t II. COMPONENT OR SYSTEM FAILURES A.
FAILURE MODE, MECHANISM, AND EFFECTS OF EACH FAILED COMPONENT i
Not applicable - there were no component failures associated with this event.
B.
DURATION OF SAFETY SYSTEM TRAIN INOPERABILITY The subject valve was not tested for 48 days beyond its violation day, and was considered inoperable for this time period.
However, the retest did not identify any degradation.
C.
SAFETY CONSEQUENCES AND IMPLICATIONS
The turbine driven auxiliary Feedwater pump (EIIS:(P)(BA)) is supplied i
with steam from Main Steam Lines (MSL) 1 and 4.
In the event that steam generator (EIIS:(SG)(SB)) 1 was to completely de)ressurize, an adequate j
amount of steam to the Turbine Driven Auxiliary eedwater Pump (TDAFP) could be supplied from steam generator 4.
In the closed position, check valve 2MS-0143 isolated the TDAFP from the depressurized steam generator, thereby ensuring that the steam from MSL 4 does not flow to the depressurized MSL 1, bypassing the TDAFP.
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However, if the steam generator 1 is depressurizing in an uncontrolled manner, the Emergency Operating Procedures direct the reactor operators to close the steam supply valves (2MS-0101 and 2MS-0144) which are located u) stream and downstream of the check valve. This instruction ensures t1at an adequate supply of steam to the TDAFP would be maintained, even if 2MS-0143 failed to close when appropriate.
Therefore, the health and safety of the public would be unaffected. by this occurrence.
III. CAUSE OF THE EVENT
The procedure for testing the Auxiliary Feed Water components delineates both i
the monthly Technical Specification, and the quarterly ASME Section XI testing requirements. As written in the purpose of the procedure. both tests appear to be identical; however, the quarterly ASME Section XI test for the check valve 2MS-0143 is aerformed in both the open and closed positions.
During recovery from the iid Cycle Outage. Operations personnel performing the required Technical Surveillance test, which is normally performed with the valve 2MS-0143 in the open position believed that the requirements for the ASME Section XI test were also satisfied.
The cause of the event was deemed to be less than adequate information in the Surveillance Work Order.
Specific information with respect to what procedure section was applicable to monthly or quarterly test was not identified on the work order.
Additionally, adequate guidance was not provided by the Operations Surveillance Coordinator as to what component required the monthly or quarterly test.
IV. CORRECTIVE ACTIONS
A review of Unit 1 surveillances for this type of surveillance was performed by the IST Coordinator, no additional matters of concerns were identified.
Moreover. during this review it was noted that, the valve in question had current valid surveillance tests.
The Surveillance Work Order for Auxiliary Feed Water testing has been revised to provide clear guidance on the monthly Technical Specification surveillance and the quarterly ASME Section XI surveillance.
To preclude recurrence TU Electric is evaluating other surveillance work orders where there may have been an absence of clear guidance with respect to similar types of surveillances. Additionally, management expectations with i
respect to clear guidance for the testing requirements has been reemphasized
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to cognizant personnel.
l V.
PREVIOUS SIMILAR EVENTS
There are other CPSES Licensee Event Reports which involve incomplete / missed surveillances involving procedure deficiencies, personnel errors, or other
causes
Management expectations have been identified and have been conveyed to appropriate personnel to eliminate this type event.
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